ML040160886

Written Exam Forms for the Prairie Island Initial Examination - Sep 2003

ML040160886
Person / Time
Site:	Prairie Island
Issue date:	09/08/2003
From:	Cooper P Nuclear Management Co
To:	NRC/RGN-III
References
50-282/03-301, 50-306/03-301
Download: ML040160886 (18)

Text

ES-401 PWR Examination Outline Form ES-401-2 RO K/A Category Points SRO-Only Points TIER GROUP K K K K K K A A A A A G TOTAL K A G TOTAL 1 2 3 4 5 6 1 2 3 4 2

1. 1. 3 3 3 3 3 3 18 0 0 5 2 7 Emergency

2. 1 2 2 1 1 2 9 0 0 4 1 5 Abnormal Plant Tier Evolutions 4 5 5 4 4 5 27 0 0 9 3 12 Totals

1. 3 2 3 2 3 2 3 3 2 3 2 28 0 0 0 4 4 2.

Plant 2. 1 1 1 1 1 0 1 1 1 1 1 10 0 0 0 2 2 Systems Tier 4 3 4 3 4 2 4 4 3 4 3 38 0 0 0 6 6 Totals

3. Generic Knowledge and 1 2 3 4 1 2 3 4 10 7 Abilities Categories 3 2 3 2 2 2 2 1 Notes:

1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the Tier Totals in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding SRO sampling.

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system or evolution unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category/tier.

6. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

NUREG-1021, Draft Revision 9 Page 22 of 34

PWR Examination Outline ES-401 Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 EA2.04: Ability to determine and interpret the following as they apply to 000007 Reactor Trip - Stabilization - Recovery a reactor trip: If reactor should have S 4.4 0/1

/1 tripped but has not done so, manually trip the reactor and carry out actions in ATWS EOP AA2.20: Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident:

000008 Pressurizer Vapor Space Accident / 3 R 3.4 1/0 The effect of an open PORV on code safety, based on observation of plant parameters EA2.14: Ability to determine and interpret the following as they apply to 000009 Small Break LOCA / 3 R 3.8 1/0 a small break LOCA: Actions to be taken if PTS limits are violated EK3.15: Knowledge of the reasons for the following responses as they apply to the Large Break LOCA: Criteria for 4.3 shifting to recirculation mode 000011 Large Break LOCA / 3 R S 1/1 (SRO) EA2.02: Ability to determine and interpret the following as they apply to a Large Break LOCA: 3.7 Consequences to RHR of not resetting safety injection AK2.08: Knowledge of the interrelations between the Reactor 000015/17 RCP Malfunctions / 4 R 2.6 1/0 Coolant Pump Malfunctions and the following: CCWS AK1.02: Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor 000022 Loss of Rx Coolant Makeup / 2 R 2.7 1/0 Coolant Pump Makeup: Relationship of charging flow to pressure differential between charging and RCS AK1.01: Knowledge of the operational implications of the following concepts 000025 Loss of RHR System / 4 R as they apply to Loss of Residual Heat 3.9 1/0 Removal System: Loss of RHRS during all modes of operation 000026 Loss of Component Cooling Water / 8 AK3.03: Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control 3.7 Malfunctions: Actions contained in EOP for PZR PCS malfunction 000027 Pressurizer Pressure Control System R S 1/1 Malfunction / 3 (SRO) 2.4.30: Emergency Procedures/Plan: Knowledge of which events related to system operations/status should be reported 3.6 to outside agencies. (Pressurizer Pressure Control Malfunction)

Page 23 of 34 NUREG-1021, Draft Revision 9

PWR Examination Outline ES-401 Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 EK2.06: Knowledge of the interrelations between the ATWS and 000029 ATWS / 1 R 2.9 1/0 the following: Breakers, relays, and disconnects EA1.27: Ability to operate and/or monitor the following as they apply to 000038 Steam Gen. Tube Rupture / 3 R 3.9 1/0 a SGTR: Steam dump valve status lights and indicators 2.4.31: Emergency Procedures/Plan:

Knowledge of annunciators alarms 000040 and W/E12 Steam Line Rupture -

R and indications, and use of the 3.3 1/0 Excessive Heat Transfer / 4 response instructions. (Steam Line Rupture)

AK3.01: Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW):

4.1 Reactor and/or turbine trip, manual and automatic 000054 Loss of Main Feedwater / 4 R S 1/1 (SRO) AA2.01: Ability to determine and interpret the following as they 4.4 apply to the Loss of Main Feedwater (MFW): Occurrence of reactor and/or turbine trip 2.2.25: Equipment Control:

Knowledge of bases in technical specification for limiting conditions for 2.5 operation and safety limits. (Station Blackout) 000055 Station Blackout / 6 S R 1/1 (SRO) EA2.02: Ability to determine and interpret the following as they 4.6 apply to a Station Blackout: RCS core cooling through natural circulation cooling to S/G cooling AA1.37 :Ability to operate and/or monitor the following as they apply to 000056 Loss of Off-site Power / 6 R 3.4 1/0 the Loss of Offsite Power: Instrument air AA2.12: Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: 3.5 PZR level controller, instrumentation, and heater indications 000057 Loss of Vital AC Inst. Bus / 6 R S 1/1 (SRO) 2.2.25: Equipment Control:

Knowledge of bases in technical specifications for limiting conditions for 3.7 operations and safety limits. (Loss of Vital AC Instrument Bus) 2.1.32: Conduct of Operations: Ability 000058 Loss of DC Power / 6 R to explain and apply all system limits 3.4 1/0 and precautions. (Loss of DC Power) 000062 Loss of Nuclear Svc Water / 4 Page 23 of 34 NUREG-1021, Draft Revision 9

PWR Examination Outline ES-401 Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 AA1.05: Ability to operate and/or 000065 Loss of Instrument Air / 8 R monitor the following as they apply to 3.3 1/0 the Loss of Instrument Air: RPS W/E04 LOCA Outside Containment / 3 EK2.2: Knowledge of the interrelations between the Loss of Emergency Coolant Recirculation and the following: Facilitys heat removal systems, including primary coolant, 3.9 emergency coolant, the decay heat removal systems, and relations between the proper operation of these W/E11 Loss of Emergency Coolant Recirc. / 4 R S systems to the operation of the facility 1/1 (SRO) EA2.1: Ability to determine and interpret the following as they apply to Loss of Emergency Coolant 4.2 Recirculation: Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

EK1.3: Knowledge of the operational implications of the following concepts as they apply to the Loss of Secondary W/E05 Inadequate Heat Transfer - Loss of R Heat Sink: Annunciators and 3.9 1/0 Secondary Heat Sink / 4 conditions indicating signals, and remedial actions associated with the Loss of Secondary Heat Sink RO 3 3 3 3 3 3 K/A Category Totals Group Point Total 18/7 SRO -- -- -- -- 5 2 Page 23 of 34 NUREG-1021, Draft Revision 9

PWR Examination Outline ES-401 Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 AA2.02: Ability to determine and interpret the following as they apply to 000001 Continuous Rod Withdrawal / 1 R 4.2 1/0 the Continuous Rod Withdrawal:

Position of emergency boration valve AA2.03: Ability to determine and interpret the following as they apply to the Dropped Control Rod: Dropped rod 000003 Dropped Control Rod / 1 S 3.8 0/1 using in-core/ex-core instrumentation, in-core or loop temperature measurements 000005 Inoperable Stuck Control Rod / 1 AA2.01: Ability to determine and interpret the following as they apply to 000024 Emergency Boration / 1 S the Emergency Boration: Whether 4.1 0/1 boron flow and/or MOVs are malfunctioning, from plant conditions 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 AK1.01: Knowledge of the operational implications of the following concepts as they apply to Loss of Intermediate 000033 Loss of Intermediate Range NI / 7 R 2.7 1/0 Range Nuclear Instrumentation:

Effects of voltage changes on performance 000036 Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. /9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 AK3.18: Knowledge of the reasons for the following responses as they apply 000068 Control Room Evac. / 8 R to the control room evacuation: 4.2 1/0 Actions contained in EOP for control room evacuation emergency task EK2.1: Knowledge of the interrelations between the High Containment Pressure and the following:

Components, and functions of control 000069 and W/E14 Loss of CTMT Integrity / 5 R 3.4 1/0 and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features NUREG-1021, Draft Revision 9 Page 24 of 34

PWR Examination Outline ES-401 Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 EK2.1: Knowledge of the interrelations between the Saturated Core Cooling and the following: Components, and functions of control and safety 3.2 systems, including instrumentation, signals, interlocks, failure modes, and 000074 (W/E06 & 07) Inad. Core Cooling / 4 R S automatic and manual features 1/1 (SRO) 2.2.25: Equipment Control:

Knowledge of bases in technical 3.7 specifications for limiting conditions for operations and safety limits.

(Inadequate Core Cooling)

AK3.06: Knowledge of the reasons for the following responses as they apply 000076 High Reactor Coolant Activity / 9 R to the High Reactor Coolant Activity: 3.2 1/0 Actions contained in EOP for high reactor coolant activity EA1.2: Ability to operate and/or W/E01 and W/E02 Rediagnosis & SI monitor the following as they apply to R 3.6 1/0 Termination / 3 the SI Termination: Operating behavior characteristics of the facility 2.1.23: Conduct of Operations: Ability to perform specific system and integrated plant procedures during all 3.9 modes of plant operation. (Steam Generator Overpressure)

W/E13 Steam Generator Over-pressure / 4 S R 1/1 (SRO) EA2.2: Ability to determine and interpret the following as they apply to the Steam Generator Overpressure:

Adherence to appropriate procedures 3.4 and operation within the limitations in the facility's license and amendments W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 W/E03 LOCA Cooldown - Depress. / 4 EA2.2: Ability to determine and interpret the following as they apply to the Natural Circulation with Steam W/E09 and W/E10 Natural Circ. / 4 S Void in Vessel with/without RVLIS: 3.9 1/0 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 2.1.23: Conduct of Operations: Ability to perform specific system and W/E08 RCS Overcooling - PTS / 4 R integrated plant procedures during all 3.9 1/0 modes of plant operation. (Pressurized Thermal Shock)

RO 1 2 2 1 1 2 K/A Category Totals Group Point Total 9/5 SRO -- -- -- -- 4 1 NUREG-1021, Draft Revision 9 Page 24 of 34

PWR Examination Outline ES-401 Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K2.01: Knowledge of bus power 003 Reactor Coolant Pump R 3.1 1/0 supplies to the following: RCPS K5.17: Knowledge of the operational implications of the following concepts 004 Chemical and Volume R as they apply to the CVCS: Types and 2.6 1/0 Control effects of radiation, dosimetry, and shielding-time-distance K6.03: Knowledge of the effect of a loss or malfunction of the following will 005 Residual Heat Removal R 2.5 1/0 have on the RHRS: RHR heat exchanger K5.06: Knowledge of the operational implications of the following concepts 006 Emergency Core Cooling R as they apply to the ECCS: 3.5 1/0 Relationship between ECCS flow and RCS pressure A3.01: Ability to monitor automatic 007 Pressurizer Relief/Quench operation of the PRTS, including:

R 2.7 1/0 Tank Components which discharge to the PRT A1.04: Ability to predict and/or monitor changes in parameters (to prevent 008 Component Cooling R exceeding design limits) associated 3.1 1/0 Water with operating the CCWS controls including: Surge tank level K1.06: Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS 2.9 and the following systems: CVCS 010 Pressurizer Pressure R R A1.01: Ability to predict and/or monitor 2/0 Control changes in parameters (to prevent exceeding design limits) associated 2.8 with operating the PZR PCS controls including: PZR and RCS boron concentrations K5.01: Knowledge of the operational implications of the following concepts 3.3 as they apply to the RPS: DNB 012 Reactor Protection R S 1/1 (SRO) 2.2.25: Equipment Control:

Knowledge of bases in technical 3.7 specifications for limiting conditions for operations and safety limits. (RPS)

K6.01: Knowledge of the effect of a loss or malfunction of the following will 2.7 have on the ESFAS: Sensors and detectors 013 Engineered Safety R S 1/1 Features Actuation (SRO) 2.2.25: Equipment Control:

Knowledge of bases in technical 3.7 specifications for limiting conditions for operations and safety limits. (ESFAS)

Page 25 of 34 NUREG-1021, Draft Revision 9

PWR Examination Outline ES-401 Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 A1.04: Ability to predict and/or monitor changes in parameters (to prevent 022 Containment Cooling R exceeding design limits) associated 3.2 1/0 with operating the CCS controls including: Cooling water flow K3.01: Knowledge of the effect that a loss or malfunction of the CSS will 3.9 have on the following: CCS A2.03: Ability to (a) predict the impacts 026 Containment Spray R R of the following malfunctions or 2/0 operations on the CSS and (b) based on those predictions, use procedures 4.1 to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of ESF 2.4.49: Emergency Procedures/Plan:

Ability to perform without reference to procedures those actions that require 4.0 immediate operation of system components and controls. (Main and Reheat Steam) 039 Main and Reheat Steam R R 2/0 K1.06: Knowledge of the physical connections and/or cause-effect 3.1 relationships between the MRSS and the following systems: Condenser steam dump A2.04: Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System and (b) based on those predictions, 056 Condensate R 2.6 1/0 use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps K3.04: Knowledge of the effect that a loss or malfunction of the MFW 3.6 System will have on the following:

RCS 059 Main Feedwater R R 2/0 A4.12: Ability to manually operate and/or monitor in the control room:

3.4 Initiation of automatic feedwater isolation Page 25 of 34 NUREG-1021, Draft Revision 9

PWR Examination Outline ES-401 Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K2.02: Knowledge of bus power supplies to the following: AFW electric 3.7 driven pumps 061 Auxiliary/Emergency K4.02: Knowledge of AFW System R R 2/0 Feedwater design feature(s) and/or interlock(s) which provide for the following: AFW 4.5 automatic start upon loss of MFW pump, S/G level, blackout, or safety injection K3.02: Knowledge of the effect that a loss or malfunction of the A.C.

4.1 Distribution System will have on the following: ED/G 062 AC Electrical Distribution R S 1/1 (SRO) 2.4.6: Emergency Procedures/Plan: Knowledge symptom 4.0 based EOP mitigation strategies. (AC Electrical Distribution)

A2.01: Ability to (a) predict the impacts of the following malfunctions or operations on the D.C. Electrical System and (b) based on those 063 DC Electrical Distribution R 2.5 1/0 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Grounds A3.03: Ability to monitor automatic operation of the ED/G System, 3.4 including: Indicating lights, meters, 064 Emergency Diesel and recorders R S 1/1 Generator (SRO) 2.2.22: Knowledge of limiting conditions for operations and safety 2.9 limits.

A4.03: Ability to manually operate 073 Process Radiation and/or monitor in the control room:

R 3.1 1/0 Monitoring Check source for operability demonstration 2.1.14: Conduct of Operations:

Knowledge of system status criteria 2.5 which require the notification of plant personnel. (Service Water System) 076 Service Water R R 2/0 A4.04: Ability to manually operate and/or monitor in the control room: 3.5 Emergency heat loads K1.05: Knowledge of the physical connections and/or cause-effect 078 Instrument Air R 3.4 1/0 relationships between the IAS and the following systems: MSIV air Page 25 of 34 NUREG-1021, Draft Revision 9

PWR Examination Outline ES-401 Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K4.04: Knowledge of Containment System design feature(s) and/or 103 Containment R interlock(s) which provide for the 2.5 1/0 following: Personnel access hatch and emergency access hatch RO 3 2 3 2 3 2 3 3 2 3 2 K/A Category Totals: Group Point Total: 28/4 SRO -- -- -- -- -- -- -- -- -- -- 4 Page 25 of 34 NUREG-1021, Draft Revision 9

PWR Examination Outline ES-401 Form ES-401-2 Plant Systems - Tier 2 / Group 2 K K K K K K A A A A Group 2 (RO / SRO) G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive A3.03: Ability to monitor automatic 002 Reactor Coolant R operation of the RCS, including: 4.4 1/0 Pressure, temperatures, and flows K2.01: Knowledge of bus power supplies to the following: Charging 3.1 pumps (SRO) 2.4.4: Emergency 011 Pressurizer Level Control R S Procedures/Plan: Ability to recognize 1/1 abnormal indications for system 4.3 operating parameters which are entry-level conditions for emergency and abnormal operating procedures..

(Pressurizer Level Control System)

K3.02: Knowledge of the effect that a 014 Rod Position Indication R loss or malfunction of the RPIS will 2.5 1/0 have on the following: Plant computer 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation A1.01: Ability to predict and/or monitor changes in parameters (to prevent 017 In-core Temperature exceeding design limits) associated R 3.7 1/0 Monitor with operating the ITM System controls including: Core exit temperature 027 Containment Iodine Removal A4.02: Ability to manually operate and/or monitor in the control room:

Location and interpretation of 3.7 containment pressure indications 028 Hydrogen Recombiner R S (SRO) 2.2.25: Equipment Control: 1/1 and Purge Control Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. 3.7 (Hydrogen Recombiner and Purge Control System) 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator K5.07: Knowledge of the operational 041 Steam Dump/Turbine implications of the following concepts R 3.1 1/0 Bypass Control as they apply to the SDS: Reactivity feedback effects NUREG-1021, Draft Revision 9 Page 26 of 34

PWR Examination Outline ES-401 Form ES-401-2 Plant Systems - Tier 2 / Group 2 K K K K K K A A A A Group 2 (RO / SRO) G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 045 Main Turbine Generator 2.1.32: Conduct of Operations: Ability to explain and apply all system limits 055 Condenser Air Removal R 3.4 1/0 and precautions. (Condenser Air Removal System)

A2.04: Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System and (b) based on those 068 Liquid Radwaste R 3.3 1/0 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Failure of automatic isolation 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water K4.01: Knowledge of SAS design feature(s) and/or interlock(s) which 079 Station Air R 2.9 1/0 provide for the following: Cross-connect with IAS K1.01: Knowledge of the physical connections and/or cause-effect 086 Fire Protection R relationships between the Fire 3.0 1/0 Protection System and the following systems: High-pressure service water RO 1 1 1 1 1 0 1 1 1 1 1 K/A Category Totals: Group Point Total: 10/2 SRO -- -- -- -- -- -- -- -- -- -- 2 NUREG-1021, Draft Revision 9 Page 26 of 34

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Prairie Island Date of Exam: 09/11/2003 RO SRO Category K/A # Topic IR # IR #

Ability to make accurate, clear and concise logs, records, status 2.1.18 2.9 1 boards, and reports.

2.1.29 Knowledge of how to conduct and verify valve lineups. 3.4 1 Ability to locate control room switches, controls and indications

1. 2.1.31 and to determine that they are correctly reflecting the desired plant 4.2 1 Conduct of lineup.

Operations Ability to maintain primary and secondary plant chemistry within 2.1.34 2.9 1 allowable limits.

Conduct of Operations: Ability to supervise and assume a 2.1.6 4.3 1 management role during plant transients and upset conditions.

Subtotal 3 2 Ability to perform pre-startup procedures for the facility, including 2.2.1 operating those controls associated with plant equipment that could 3.7 1 affect reactivity.

Ability to explain the variations in control board layouts, systems, 2.

2.2.4 instrumentation and procedural actions between units at a facility. 2.8 1 Equipment (multi-unit)

Control Knowledge of bases in technical specifications for limiting 2.2.25 3.7 1 conditions for operations and safety limits.

2.2.32 Knowledge of the effects of alterations on core configuration. 3.3 1 Subtotal 2 2 Knowledge of 10 CFR 20 and related facility radiation control 2.3.1 2.6 1 requirements.

Ability to perform procedures to reduce excessive levels of 2.3.10 2.9 1 radiation and guard against personnel exposure.

3. 2.3.9 Knowledge of the process for performing a containment purge. 2.5 1 Radiation Knowledge of radiation exposure limits and contamination control, 2.3.4 3.1 1 Control including permissible levels in excess of those authorized.

Knowledge of SRO responsibilities for auxiliary systems that are 2.3.3 outside the control room (e.g., waste disposal and handling 2.9 1 systems).

Subtotal 3 2 Knowledge of EOP implementation hierarchy and coordination 2.4.16 3.0 1 with other support procedures.

4.

Ability to recognize abnormal indications for system operating Emergency 2.4.4 parameters which are entry-level conditions for emergency and 4.0 1 Procedures abnormal operating procedures.

/ Plan 2.4.27 Knowledge of fire in the plant procedure. 3.5 1 Subtotal 2 1 Tier 3 Point Total 10 7 NUREG-1021, Draft Revision 9 Page 26 of 34

Level /

Randomly Tier / Reason for Rejection Selected K/A Group We have no technical reference for this K/A. Knowledge of the reasons for the following responses as they apply to the Large RO/1/1 011 EK3.09 Break LOCA: Maintaining D/Gs available to provide standby power We have no technical reference for this knowledge. Knowledge of the operational implications of the following concepts as they RO/1/1 022 AK1.04 apply to Loss of Reactor Coolant Pump Makeup: Reason for changing from manual to automatic control of charging flow valve controller Very difficult to turn into a good written question. This K/A is RO/1/1 055 2.1.30 sufficiently covered by the walkthrough.

This generic K/A refers to T.S. LCO entry conditions which are SRO/1/2 024 2.1.33 NOT SRO-only knowledge.

This system K/A combination was too similar to the Tier 1 K/A 000027-2.4.30. Deleted because alternate question could not be SRO/2/2 011 2.4.30 written and we did not want double jeopardy on the associated procedure.

SRO/1/1 WE11 EK1.2 The KA is not tied to 10CFR55.43.

SRO/1/2 003 AK1.03 The KA is not tied to 10CFR55.43.

SRO/2/1 012 K3.02 The KA is not tied to 10CFR55.43.

SRO/2/1 064 K6.07 The KA is not tied to 10CFR55.43.

This generic K/A refers to system function or purpose which is SRO/1/2 024 2.1.27 NOT SRO-only knowledge.

RO/2/1 078 K1.02 This KA is a duplicate to another KA already selected 079 K4.01.

Use of this KA creates double jeopardy for the Instant SRO RO/1/2 068 AA2.05 candidates via KA 055 EA.02.

NUREG-1021, Draft Revision 9 Page 26 of 34